Analysis of severe accident on OPR1000 PWR plant at low power and shutdown states with MAAP5 code
Creators
- 1. Nuclear Reactor Safety Laboratory, Central Research Institute of Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)
Description
The objective of this paper is to provide a brief description of severe accident analysis using computer codes in Korean OPR1000 Plant at low power and shutdown states. The results of the analysis are utilized in preparing the shutdown severe accident management guidelines (LPSD SAMG). As part of the efforts to prepare LPSD SAMG, analysis of severe accident is performed at low power and shutdown states with MAAP5 code. The Korean OPR1000 plant, a PWR plant with 2 hot legs and 4 cold legs is considered as a reference plant in the analysis. In this study, the scenarios are selected based on the plant operational states (POS) and dominant initiating events (IE) which cause the core damages. Typical scenarios are the loss of shutdown cooling (LSCS) at various primary coolant levels and stuck-opening of valves which prevent the low temperature over pressurization (LTOP) of primary system. As the analysis results, the core uncovery is expected in 2∼6 hours. The maximum temperature of core exit exceeds 649degC (SAMG entry temperature) in 3∼7 hours. The molten corium starts to relocate into lower head in 5∼13 hours and reactor vessel failure is occurred in 11∼14 hours. The above mentioned timings are utilized to choose the possible actions and the timing to implement those actions LPSD SAMG. Also based on the results, the environmental conditions that instruments may encounter in a severe accident are determined. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
- Imprint Pagination
- 2846 p.
- Journal Page Range
- 10 p.
Conference
- Title
- 10. international topical meeting on nuclear thermal hydraulics, operation and safety
- Acronym
- NUTHOS-10
- Dates
- 14-18 Dec 2014
- Place
- Ginowan, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47048857
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; M CODES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; REACTOR SHUTDOWN; RISK ASSESSMENT; TIME-SERIES ANALYSIS
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MATHEMATICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SHUTDOWN; SIMULATION; STATISTICS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1304.pdf; 4 refs., 4 figs., 6 tabs.